ML20077R945
| ML20077R945 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 01/11/1995 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20077R939 | List: |
| References | |
| NUDOCS 9501230205 | |
| Download: ML20077R945 (7) | |
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4 ATTACHMENT 2
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TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES LICENSE AMENDMENT APPLICATION REMOVAL OP' TUR.BINE OVERSP3ED PROTECTION i
FROM THE TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NPF-57 i
HOPE CREEK GENERATING STATION NLR-N94173 DOCKET NO. 50-354 LCR 94-25 The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this License Amendment Request:
Bchnical Specification Paces 3/4.3.8 ix and xviii
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3/4.3.8 3/4 3-103 and 3/4 3-104 B 3/4.3.8 B 3/4 3-7 i
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9501230205 950111 PDR ADOCK 05000354 P
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INDEX LIMITING CONDITIONS FOR OPERATION AND CURVEILLANCE REQUIREMENTS SECTION PAGE Table 3.3.7.4-1 Remote Shutdown Monitoring Instrumentation.........................
3/4 3-75 Table 3.3.7.4-2 Remote Shutdown Systems Controls........
3/4 3-77 Table 4.3.7.4-1 Remote Shutdown Monitoring Instrumentation Surveillance Requirements............................
3/4 3-82 Accident Monitoring Instrumentation...
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3/4 3-E4 Table 3.3.7.5-1 Accident Monitoring Instrumentation.....
3/4 3-85 Table 4.3.7.5-1 Accident Monitoring Instrumentation Surveillance Requirements..............
3/4 3-87 Source Range Monitors..................
3/4 3-88 Traversing In-Core Probe System..........................
3/4 3-89 Loose-Part Detection System...............................
3/4 3-90 Radioactive Liquid Ef fluent Monitoring Instrumentation....
3/4 3-91 Table 3.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation..............
3/4 3-92 Table 4.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements............................
3/4 3-94 Radioactive Gaseous Effluent Monitoring Instrumentation...
3/4 3-96 Table 3.3.7.10-1 Radioactive Gaseous Effluent Ref ut ud4 Monitoring Instrumentation.............
3/4 3-97 l
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~ Radioactive Gaseous Effluent Monitoring Table 4.3.7.10-1
- Instrumentation Surveillance Requirements...........................
3/4 3-100 3/473.8 TURBINEOVERSPEEDPROTECTIONSYSh......................
3/4 3-103 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTU/. TION INSTRUMENTATION...........................................
3/4 3-105 Table 3.3.9-1 Feedwater/ Main Turbine Trip System Actuation Instrumentation.................
3/4 3-106 HOFE CREEK ix
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iN0EX BASES SEC'!ON PAGE INSTRUMENTATION (Continued)
Seismic Monitoring Instrumentation...
B 3<4 3-4 Meteorological Monitoring Instrumentation...........
B 3/4 3-4 Remote Shutdown Monitoring Instrumentation and Controls....................................
B 3/4 3-5 Accident Monitoring Instrumentation.........
B 3/4 3-5 Source Range Monitors.......................
B 3/4 3-5 Traversing In-Core Probe System..................... B 3/4 3-5 Loose-Part Detection System.......
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B 3/4 3-6
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Ne/ 4c8 Radioactive Liouid Effluent Monitoring pM4 Instrumentation.....
B 3/4 3-6 losM I Radioactive Gaseous Effluent Monitoring Instrumentation..............
B 3/4 3-6
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d74.3.8 TURBINE OVERSPEED PROTECTION SYSTE.M)..
B 3/4 3-7 3/4.3.9 FEE 0 WATER /Mi!N TURBINE TRIP SYSTEM ACTUAT.*0N INSTRUMENiATION...
B 3/4 3-7 Figure B1/4 3-1 Reactor vessel Water Level...
B 3/4 3 8 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM...
B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES.
B 3/4 4-la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems...
B 3/4 4-3 Operational Leakage..................................
B 3/4 4-3 3/4.4.4 CHEMISTRY...............
B 3/4 4-3 3/4.4.5 SPECIFIC ACTIVITY..........
B 3/4 4-4 3/4.4.6 PRESSURE / TEMPERATURE LIMITS....................
B 3/4 4 5 Table 83/4.4.6-1 Reactor Vessel Toughness...
B 3/4 4-7 Figure 83/4.4.6-1 Fast Neutron Fluence (E>1Mov) at (1/4)T as a
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Function of Service Life......
B 3/4 4-B HOPE CREEK xviii Amendment No. 3
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, INSTRUMENTATION
[3/4.3.8/URBINEOVER D PROTECTIO STEM
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L TING CONDIT N FOR OPERATI 1
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3.3.8 At ast one turbi overspeed prot tion system s 1 be_ OPERABLE.
APPLIC ILITY:
OPER ONAL CONDITIONS and 2.
ACTk:
a.
With ne turbine cont valve, or o main stop valve r high pressur a
tu ine steam lead operaole and/
with one combin intermediate Ive per low pre ure turbine s am lead inoperab restore tne inoperable valv s) to OPERAB status within 72 tours or close c*
least one va e in the affe ed steam lead (s) isolate the t ine from the s am supply wit n the next 6 hou b.
With t above requir turbine overspe protection sys otherwise
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inop able, within hours isolate.t turbine,from t steam supply.
SURVEIL CE REQUIREM S
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1 4.
8.1 The pro sions of Specifi tion 4.0.4 are applicable.
4.3.8.2 Th bove required tu ine overspeed p tection syste shall be demonstra d OPERABLE:
At least once er 7 days by:
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1.
Cyc g each of the f lowing valves chrough at le one.
c late cycle fro he running p tion:
a)
For the o rspeed protec on control sy' es; l) x low pressur combined int diate valv b) r the electri 1 overspeed t p system an he mechani al overspeed tri system; 1)
Fou igh pressure in stop val s, and i
2) ix low pressu combined i reediate v ves.
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<.i HOPE CREEK 3/4 3-103 Amendment No.19 V
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hSTRUMENTATIOV SURVEILLINCEREQUIRETS (Continu )
b.
At once p 31 days by:
1.
Cycli each of the fo)1 - ing valves the ogh at least one c
ete cycle from e running posit n:
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Fe-the ov specd protectio control system; 1)
F r high pressu turbine control ves b)
F the electrica overspeed trip em and the chanica' ove ed trip system-1)
Four h pressure tu e control valve c.
t least once p 18 months by p orinance of a C EL CALIBRATIO of the turbi overspeed prote ion instrumenta n.
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d.
At less nee per 40 mont by disassembli at least one each of the a ve valves and p orming a visualj nd surface ins ction of al alve seats, dis and stems and efifying no una eptable flaws excessive corr on.
If unaccep ble flaws or essive corro on j are found, all er valves of t type shall b nspected.
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liN gqlace b
HOPE CRICK 3/4 3-104
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INSTRUMENTATION BASES
/4.St8 TURBINEJhERSPEEDPRIECTIONSYSJfM This spe fication i provided t ensure that e turbine ov speed rotection stem instr entation a the turbine peed control alves are OPERABLE a d will prot t the turb'ne from exce ive overspee.
Protecti from tur ne excessi overspeed s required nce excessiv overspeed the
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turbin could gener te potenti ly damaging issiles whic could impa and
(_dama safety rel ed compone ts, equipmen or structure i
3/4.3.9 FEE 0 WATER / MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATIO_N_
i The feedwater/ main turbine trip system actuation instrumentation is pro-vided to initiate action of the feedwater system / main turbine. trip system in the event of a high reactor vessel water level (Level 8) to mitigate potential l
damage to the main turbine.
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